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Volume 319

Nuclear Engineering and Design

Volume 319

1

Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods

Sanchez-Saez, F., Carlos, S., Villanueva, J.F., Sanchez, A.I., Martorell, S.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.01 MB

english, 2017

2

Investigations on the availability of second shutdown system of Indian FBR

Patri, Sudheer, Vijayashree, R., Suresh Kumar, S., Anup Kumar, P., Sabih, Muhammad, Chandramouli, S., Narayana Rao, P., Meikandamurthy, C., Prakash, V., Selvaraj, P.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 5.75 MB

english, 2017

3

Numerical prediction of flow induced vibrations in nuclear reactor applications

ter Hofstede, E., Kottapalli, S., Shams, A.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.38 MB

english, 2017

4

Simulations of single- and two-phase shock tubes and gravity-driven wave problems with the RELAP-7 nuclear reactor system analysis code

Delchini, Marc O., Ragusa, Jean C., Berry, Ray A.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.03 MB

english, 2017

5

Study on gas-liquid two-phase all-characteristics of CAP1400 nuclear main pump

Lu, Yonggang, Zhu, Rongsheng, Wang, Xiuli, Fu, Qiang, Li, Mengyuan, Si, Xiangyu

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.42 MB

english, 2017

6

Three-dimensional hydrodynamic modeling of the second shutdown system of an experimental nuclear reactor

Rechiman, Ludmila M., Cantero, Mariano I., Caccia, Federico A., Chacoma, Andrés, Dari, Enzo A.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 2.68 MB

english, 2017

7

Neutronic design and evaluation of a PWR fuel assembly with accident tolerant-Fully Ceramic Micro-Encapsulated (AT-FCM) fuel

Qasim Awan, M., Cao, Liangzhi, Wu, Hongchun

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 4.78 MB

english, 2017

8

Inverse uncertainty quantification of TRACE physical model parameters using sparse gird stochastic collocation surrogate model

Wu, Xu, Mui, Travis, Hu, Guojun, Meidani, Hadi, Kozlowski, Tomasz

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 2.54 MB

english, 2017

9

A sequential-parallel interdependent complement scaling approach with its applications to AP1000 passive containment cooling system

Li, Cheng, Li, Le, Li, Junming, Zhang, Yajun

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 2.05 MB

english, 2017

10

Distributed temperature sensing inside a 19-rod bundle

Lomperski, S., Bremer, N., Gerardi, C.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 2.84 MB

english, 2017

11

Numerical investigation on the dissolution kinetics of ZrO 2 by molten zircaloy using MPS method

Chen, Ronghua, Li, Yonglin, Guo, Kailun, Tian, Wenxi, Qiu, Suizheng, Su, G.H.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 3.35 MB

english, 2017

12

Decay heat uncertainty for BWR used fuel due to modeling and nuclear data uncertainties

Ilas, Germina, Liljenfeldt, Henrik

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.22 MB

english, 2017

13

Computational modeling of bubble coalescence in a high-pressure steam-water flow

Owoeye, Eyitayo James, Schubring, DuWayne

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 3.39 MB

english, 2017